Federal emergency management agency fema rep-2, rev. 2 / June 1990

lxxiii American Conference of Governmental Industrial Hygienists, “Air Sampling Instruments for Evaluation of Atmospheric Contaminants,” 5^th Edition, (1978).

lxxiv Ibid., U.S. Federal Emergency Management Agency, Guidance on Offsite Emergency Radiation Measurement Systems Phase 2 – The Milk Pathway.

lxxv Ibid., U.S. Federal Emergency Management Agency, Guidance on Offsite Emergency Radiation Measurement Systems Phase 3 – Water and Non-Dairy Food Pathway.

lxxvi Ibid., U.S. Nuclear Regulatory Commission and Federal Emergency Management Agency.

lxxvii G.R. Hoenes and J.K. Soldat, Age-Specific Radiation Dose Commitment Factors for a One-Year Chronic Intake, NUREG-0712 (November 1977).

lxxviii Ibid., U.S. Environmental Protection Agency.

lxxix Ibid., U.S. Nuclear Regulatory Commission and Federal Emergency Management Agency.

lxxx Ibid., U.S. Nuclear Regulatory Commission and U.S. Environmental Protection Agency.

lxxxi U.S. Nuclear Regulatory Commission, Manual of Respiratory Protection Against Airborne Radioactive Materials, NUREG-0041 (October 1975).

lxxxii Ibid., U.S. Federal Emergency Management Agency, Guidance on Offsite Emergency Radiation Measurement Systems Phase 2-The Milkway Pathway.

lxxxiii Ibid., U.S. Federal Emergency Management Agency, Guidance on Offsite Emergency Radiation Measurement Systems Phase 3- Water and Non-Dairy Food Pathway.

lxxxivAPPENDIX A – REFERENCES
^ Federal Register¸ “Federal Radiological Emergency Response Plan (FRERP); Currerence by All Twelve Federal Agencies and Publication as an Operational Plan,” Vol. 50, No. 217; pp 46542-46570.

lxxxv Edgerton, Germeshausen, and Grier, Inc., Las Vegas Area Operations, An Overview of the Aerial Radiological Measuring System (ARMS) Program EGG-1182-1637 (March 1975).

lxxxvi D.P. Colton, An Aerial Radiological Survey of the Three Mile Island Nuclear Station, Report No. EGG-10282-1021, Las Vegas, NV: EGG/EM (August 1983).

J.E. Jobst, “The Aerial Measuring Systems Program,” Nuclear Safety, Vol. 20, No. 2, (March-April 1979).

J.E. Jobst, “The Aerial Measuring Systems Program,” Nuclear Safety, Vol. 20, No. 2, (March-April 1979).

lxxxvii L.J. Deal and J.F. Doyle, III, An Overview of the Aerial Radiological Measuring System (ARMS) Program, Report No. EGG-1183-1637, Las Vegas, NV: EGG/EM (March 1975).

lxxxviii Ibid., D.P. Colton.

lxxxix Edgerton, Germeshausen and Grier, Inc., Santa Barbara Division, Aerial Radiological Measuring Systems (ARMS) Equipment and Procedures through FY-66 EGG-1183-2083, S-323-R (March 1966).

xc Ibid., D.P. Colton.

xci M.H. Dickerson, et. Al., Lawrence Livermore National Laboratory, ARAC Status Report: 1985, UCRL-53641 (May 1985).

xcii U.S. Environmental Protection Agency, EPA Assessment of Fallout in the United States from Atmospheric Nuclear Testing on September 26 and November 17, 1976, by the People’s Republic of China EPA-52015-77-002, (August 1977).

xciiiAPPENDIX B – REFERENCES

^ Code of Federal Regulations, Title 10 – Energy Chapter 1- Nuclear Regulatory Commission, Pt. 50, Appendix A, “General Design Criteria for Nuclear Power Plans.”

xciv U.S. Nuclear Regulatory Commission, Regulatory Guide 1.97, “Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plan and Environs Conditions During and Following and Accident,” Rev. 2 (December 1980).

xcv J.M. Selby, et al., Technological Considerations in Emergency Instrumentation Preparedness: Phase II-A-Emergency Radiological and Meteorological Instrumentation Criteria for Reactors, BNWL-1635 (May 1972).

xcvi U.S. Nuclear Regulatory Commission, Regulatory Guide 1.23, “Onsite Meteorological Programs” (February 1972).

xcvii Ibid., U.S. Nuclear Regulatory Commission and Federal Emergency Management Agency.

xcviii


^ Ibid.

xcix U.S. Environmental Protection Agency, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, EPA-520/1-75-001 (September 1975). Also see U.S. EPA’s Manual of Protective Actions for Nuclear Incidents, EPA-520/1-75-001A (January 1990).

c Ibid.

ci Ibid.

cii Ibid.

ciii Ibid.

civ M.H. Dickerson, et. Al., Lawrence Livermore National Laboratory, ARAC Status Report: 1985, UCRL-53641 (May 1985).

cvAPPENDIX C – REFERENCES
^ U.S. Nuclear Regulatory Commission, Reactor Safety Study, WASH1400, NUREG 75/015, Appendix V (1975).

cvi U.S. Nuclear Regulatory Commission, Regulatory Guide 1.3, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactor," Rev. 2 (1974).

cvii U.S. Nuclear Regulatory Commission, Regulatory Guide 1.4, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors," Rev. 2 (1974).

cviii U. S. Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculations of Annual Dose to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," (1977).

cixAPPENDIX D- REFERENCES
^ U.S. Nuclear Regulatory Commission and Federal Emergency Management Agency, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants, NUREG-O654/FEMA-REP-1, Rev. 1 (November 1980).

cx American National Standards Institute, Standard N320-1979, "American National Standard Performance Specifications for Reactor Emergency Radiological Monitoring Instrumentation."

cxi S. K. Bird, R. L. Hutchton, B. G. Motes, Mechanical Reliability Evaluation of Alternate Motors for Use in a Radioiodine Air Sampler, NUREG/CR-3513, WINCO-1006 (March 1984).

cxii C. Distenfeld and J. Klemish, An Air Sampling System for Evaluating he Thyroid Dose Commitment Due to Fission Products Released From Reactor Containment, NUREG/CR-0314 (December 1978).

cxiii S.A. McGuire, R. L. Huchton, and B. G. Motes, "Measuring Radioiodine in the Environment After A Nuclear Power Plant Accident," Proceedings of the U. S. Nuclear Regulatory Commission Eleventh Water Reactor Safety Research Information Meeting, National Bureau of Standards, Gaithersburg, Maryland, October 24-28. 1983. NUREG/CP-0048, Vol. 6, pp. 59-73.

C. Phillips and R. Lieberman, U. S. Environmental Protection Agency, Eastern Environmental Radiation Facility, Montgomery, Alabama, personal communication about "Zenon Retention on Silver Impregnated Silica Gel, Silver Zeolite, and Silver Alumina Cartridges" (February 1985).

cxiv Ibid., S.A. McGuire et al.

cxv Ibid., S.A. McGuire et al.

C. A. Pelletier, "Behavior and Measurement of Radionuclides in Effluents and the Environment," presented at the Professional Enrichment Program of the 1984 Annual Health Physics Society Meeting, New Orleans, Louisiana (June 8, 1984).

cxvi Ibid., C. A. Pelletier.

cxvii Ibid.

cxviii Ibid., C. Distenfeld and J. Klemish.

cxix U. S. Nuclear Regulatory Commission, Reactor Safety Study. App. VI, WASH 1400/NUREG 75-014 (1975).

cxx J. F. Krupa, S. K. Bird, and B. G. Motes, Evaluation of Portable Instruments for Emergency Response Measurement of Radioiodine, NUREG/CR-2267, WINCO-1003 (March 1984).

cxxi Ibid., U. S. Nuclear Regulatory Commission and Federal Emergency Management Agency.

cxxii

APPENDIX E – REFERENCES

^ American National Standards Institute, Standard N320-1979, “American National Standard Performance Specifications for Reactor Emergency Radiological Monitoring Instrumentation.”

cxxiii American National Standards Institute, Standard N13. 4-1971, “American National Standard for the Specification of Portable X- or Gamma-Radiation Survey Instruments.”

cxxiv Ibid., American National Standards Institute, Standard N320-1979.

cxxv American National Standards Institute, Standard N328-1978, “American National Standard Radiation Protection Instrumentation Test and Calibration.”

cxxvi U.S. Environmental Protection Agency, Manual of Protective Actions for Nuclear Incidents, EPA-520/1-75-001A (January 1990).

cxxvii Ibid.

cxxviii American National Standards Institute, Standard N322-1977, “American National Standard Inspection and Test Specifications for Direct and Indirect Reading Quartz Fiber Pocket Dosimeters.”

cxxix U.S. Nuclear Regulatory Commission and Federal Emergency Management Agency, Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plans, NUREG-0654/FEMA-REP-1, Rev. 1 (November 1980).

cxxx American National Standards Institute, Standard N42. 6-1980, “American National Standard Interrelationship of Quartz – Fiber Electrometer Type Exposure Meters and Companion Exposure Meter Chargers.”

cxxxi American National Standards Institute, Standard N13.11-1983, “American National Standard for Dosimetry – Personnel Dosimetry Performance – Criteria for Testing.”

cxxxii U.S. Department of Commerce, National Bureau of Standards, The National Personnel Radiation Dosimetry Accreditation Program, NBSIR 86-3350 (January 1986).

cxxxiii Ibid.

cxxxiv Ibid.

cxxxv Ibid., American National Standards Institute, Standard N13.11-1983.

cxxxvi U.S. Department of Commerce, National Bureau of Standards, 1986-87 Directory of NVLAP Accredited Laboratories, NBSIR 87-3519 (January 1987, revised annually).

***Predecisional draft – Do not cite or quote***

Directory: media-library-data
media-library-data -> Availability notice
media-library-data -> Environmental Assessment Horizon Monitoring and Surveillance Facility Puerto Nuevo Port Complex, San Juan, Puerto Rico
media-library-data -> Final hurricane script
media-library-data -> Listing of Disaster Recovery Funding Resources
media-library-data -> Nfip perspectives: History & Background Transcript